The yield of 49, the efficiency of production of 49, and poisoning in a power plant are discussed. Only the crudest of estimates of the poisoning are possible: these indicated that production will probably not be hampered by poisoning. In this case the yield of 49 could be as high as 3 kg/ton but only about 2 kg/ton is compatible with a fairly high efficiency. In the case that production is stopped by poisoning, smaller yields, proportional to the tolerable loss in k, are obtained. In this case the yield will be improved by a factor of 2 or 3 if only the most poisoned parts are extracted and replaced by new uranium.

Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from several organic materials including those suggested by the physiological shield have been extended to include both beta and deuteron bombardments. Samples of "Press-wood" are being evaluated. The effect of current on the H2O2 production in water containing I- has been studied at several I- concentrations. Water contain-dissolved CO2 shows the presence of oxidant (presumably H2O2). H2O2 has been produced by recoil protons from the scattering of fast neutrons in de-oxygenated water. Radioactive solutions do not greatly affect the applicability the glass electrode providing the electrode is thoroughly washed with distilled water before immersion in the standard buffer solution.

Abstract: Measurements are reported of the solubility of uranyl sulfate in water at several temperatures, of the density of uranyl sulfate solutions as a function of concentration, of the variation of density of uranyl sulfate solutions of three different concentrations over a temperature range from 0[degree]C. to about 93[degree]C., and of the pH of uranyl sulfate solutions as a function of concentration as well as of temperature. The pH measurements were taken on uranyl sulfate samples prepared in several different ways and some conclusions are drawn as to the purity of theses samples.

Aluminum oxide occupies a larger volume than the aluminum it contains would fill as metal, consequently, the assumption has been made that holes in metallic aluminum would close by a sufficient amount of oxidation. Therefore, we were asked to investigate the rate of plug formation under conditions to be expected in the pile. For the latter we were requested to approach the pile conditions as nearly as we could by employing the Chicago cyclotron. It seems to us that the problem divides itself into two separate questions: (1) under what conditions may holes be expected to close? (2) if holes do close how much corrosion of uranium may be expected before the closure becomes impervious to water vapor? In this report only the first question is considered. The experiments and theory coupled with the data collected by other workers on the project definitely define the limits within which pores in the aluminum cans may be expected to close by an oxidation process. Under the most favorable conditions only small holes may be sealed in this manner. In the large majority of the cases the holes not only fail to close but become larger.

Abstract. the electrodeposition of uranium metal, in the form of tree-like deposits, from molten strontium halide baths is described. Under the best conditions studied, approximately 40% recovery is attained. Freedom from side-reactions of the reduced uranium with anode products and/or refractory materials, and high cathode current densities appear to be essential to the success of the process. the refining of uranium under similar conditions appears to occur quite readily, with approximately 50% current efficiency. The preparation of UI3 is also described.

Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating conditions.

Abstract. The effect of the neutron flux on the relative importance of different fission product poisons is discussed. The general expression for the poising of a fission product is given with the various equations for special cases of interest. The formulae are applied to the problem of finding the poisoning due to fission products at the end of one day in a pile operating with a flux of 4 x 10(14) neutrons/cm(2)/soc. These results are summarized in the table on page 12. Appendix I contains a revised list of cross sections x yields for all stable isotopes. Such a list was first given by Wheeler in CP-889. Appendix II contains a list of radioactive fission products with half lives greater than one day with data about yields, parents, gaseous ancestors, and numbers of neutrons.

This report details an experiment undergone to determine the amount of radioactive strontium, barium-lanthanum, fission mixture, and sodium accumulated by and distributed within non-feeding goldfish. The report includes tables detailing the findings.

Technical report with short reports on (1) Effect of radiation on water and aqueous systems; (2) Gas evolution from uranyl solutions; (3) Effect of radiation on solid compounds; (4) Instruments; and (5) Scattering.

Technical report discussing that the deuterium concentration of heavy water can be determined by equilibrating the water with deuterium gas in the presence of a catalyst with subsequent analysis of the equilibrated gas on the mas spectrometer. The apparatus for equilibration analyses maybe be considered in three parts: 1) apparatus for introducing the ingredients into the reaction chambers; 2) the reaction chambers; 3) the mass spectrometer for analysis of the equilibrated gas. The isotopic composition of the deuterium gas to be used as the starting material is primarily governed by what gases are available. In general it is best to use gas within about one percent on either side of the final equilibrium composition. No reaction takes place between deuterium gas and water molecules in the absence of a catalyst. Platinum oxide is used as the catalyst.

Abstract: The velocity of sound at the time of 100-ton shot at Trinity was measured to be 1116.1 ft/sec. Values of blast pressure computed from the excess velocity are given, but are not considered as reliable.

From abstract: "A chamber was constructed with three electrodes dividing the space into two regions of 800 c.c. The surfaces of one of these were coated with boron carbide. With opposite potentials on two electrodes, ion currents to the collecting electrode due to gamma rays were practically cancelled and ion currents due to alpha rays induced by slow neutrons were measured."

Introduction. Some forty different uranium compounds have now been given diffraction study at Ames. Reports of these investigations are scattered in the Project literature; many have been reported in a sentence or two as a note along with chemical or metallographic reports. To make the results of this crystal structure work more available this summary of the Ames work has been compiled. (A similar summary has already been published from the Chicago laboratory.)

The following document discusses general theories of hydrogen peroxide decomposition.

Report discussing the preparation, stability, and recommended storage of cobalt trifluoride. "Cobalt trifluoride prepared by the action of fluorine upon anhydrous cobalt dichloride remains stable when kept in sealed glass tubes but on exposure to air it absorbs water and its use in the conversion of T3O8 to TF6 cannot be relied upon..."

Technical report regarding he purpose of the investigation was to evaluate the Chicago mass spectrograph as an analytical instrument for solids.

Report discussing "methods for the manufacture of refractory crucibles for use in high temperature work in general." Additionally, "preliminary experiments with the induction furnace to test the action of tantalum on tantalum carbide at 2900°C are described."

Report discussing the practice of using methyl methacrylate as a coating for platinium dishes in fluorescence method of uranium analysis. The experimental procedure described in this report to evaluate this practice indicates that the sample would be sufficiently protected from contamination and would not need to be stored in a desiccator.

The following report discusses the deposition of radioactive elements during a nuclear fission in the skeleton. Studies are concerned with chronic effects of toxic radiation developing within the bone marrow and decontaminating the cells.

Abstract. The distribution coefficient of U(VI) between perchloric acid solutions and benzene solutions of TTA has been measured as a function of the acidity. It was possible to interpret the data in terms of the charge on the U(VI) species present in the aqueous phase. The experiments indicate that U(VI) exists as an ion charge +2 at acidities from 0.1M to 2.5M. In the interpretations of the distribution data, it was necessary to know the acidity coefficient of the uranyl chelate in the benzene solution. This was determined by measurement of the solubility of the compound UO2K2 - xH2). The activity coefficient of UO2K2 was found to decrease rapidly as the concentration of TTA in the benzene phase increased above 0.1M. This is probably due to the formation of a species involving more than two TTA molecules per U(VI)

From introduction: "The purpose of this report is to summarize some of the information obtained to date on the distribution of the uranium in the mineral phases of the phosphate rocks and shale."

Abstract: "It has been found that the two principal uranium isotopes exhibit slightly different arc spectra. Certain U-235 lines have been found to be displaced from corresponding U-238 lines by about one reciprocal centimeter. The intensity ratio, IU235/IU238, has been shown to be a steadily increasing function of the U-235 concentration. These data indicate the possibility of developing a method for the determination of isotopic concentration by means of emission spectra."

The following preliminary report describes obliquity factors for shields of various shapes.

The following report summarizes research done on dissolving uranium from phosphate rock and superphosphate and recovering it from solution in a more concentrated form.